Gravity dominated two-phase flow in vertical rod bundles
Description
The fluid flow configuration through the core during reflood in a Loss-of-Coolant-Accident in a reactor is investigated. Both, cold leg injection and the cold leg + upper plenum injection are studied. The core behavior is dependent primarily on whether the core in un-flooded, partially-flooded or flooded. This work deals mainly with the un-flooded core. For an un-flooded core, the flow transition from counter-current slug flow to counter-current annular flow is inlet geometry dependent and occurs due to vapor bubble trapping. A method is developed to predict the range of down-flow liquid velocities for which the bubble is trapped. Flow reversal (or dump) through the core occurs if pressure in the upper plenum becomes more than the pressure in the lower plenum. Due to high down-flow liquid velocities in flow reversal, the upper plenum is drained of liquid very quickly and an oscillation down-flow develops. In most of the cases, a one-dimensional analysis, using an average heat flux, provides reasonably accurate predictions
Availability note (English)
MF available from INIS under the Report Number; NTI.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 171 p.
- Report number
- NUREG/CR--1218
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11531428
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS